Contribution of the JRC to the development of neutron resonance densitometry to characterize melted fuel from severe accidents
溶融燃料の核物質測定のための中性子共鳴濃度分析法に対するJRCの貢献
Schillebeeckx, P.*; Becker, B.*; Emiliani, F.*; Kopecky, S.*; Kauwenberghs, K.*; Moens, A.*; Mondelaers, W.*; Sibbens, G.*; 原田 秀郎 ; 北谷 文人; 小泉 光生; 呉田 昌俊; 飯村 秀紀; 高峰 潤; 土屋 晴文; Abousahl, S.*; Moxon, M.*
Schillebeeckx, P.*; Becker, B.*; Emiliani, F.*; Kopecky, S.*; Kauwenberghs, K.*; Moens, A.*; Mondelaers, W.*; Sibbens, G.*; Harada, Hideo; Kitatani, Fumito; Koizumi, Mitsuo; Kureta, Masatoshi; Iimura, Hideki; Takamine, Jun; Tsuchiya, Harufumi; Abousahl, S.*; Moxon, M.*
JAEA and EC-JRC started a collaboration to study Neutron Resonance Densitometry (NRD) as a method for the characterization of melted fuel formed in nuclear accidents. NRD is based on a combination of Neutron Resonance Transmission Analysis (NRTA) and Neutron Resonance Capture Analysis (NRCA). In this presentation, the contribution of the EC-JRC-IRMM to the project is discussed. Within the project the GELINA facility will be used to validate the method and perform tests on calibration and test samples. In a first exercise the test samples will not contain actinides, however, they will contain nuclides having similar characteristics as the melted fuel for NRCA and NRTA. These samples will be produced and characterized at dedicated laboratories of our institute. To study the impact of the sample characteristics, in particular the particle size distribution of powder samples, various analytic models are compared. In addition stochastic simulations are used to select a specific model and to estimate the uncertainties introduced by the model. The stochastic model is also used to verify bias effects due to sample properties. The results of the simulations are verified by measurements at GELINA. In addition, the data reduction and analysis procedures will be adapted such that they can be used for in-field application of NRD. The changes required for NRD applications are discussed.
使用言語 : English
掲載資料名 : Proceedings of INMM 54th Annual Meeting (CD-ROM)
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ページ数 : 7 Pages
発行年月 : 2013/07
出版社名 :
発表会議名 : INMM 54th Annual Meeting
開催年月 : 2013/07
開催都市 : Palm Desert
開催国 : U. S. A.
特許データ :
PDF :
論文URL :
キーワード : 福島第一原子力発電所事故; Fukushima Daiichi Nuclear Power Station Accident
使用施設 :
広報プレスリリース :
論文解説記事
(成果普及情報誌)
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受委託・共同研究相手機関 : JRC-IRMM
 
登録番号 : BB20123506
抄録集掲載番号 : 42000100
論文投稿番号 : 13640
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